ML102080325
| ML102080325 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 08/02/2010 |
| From: | Bruce Watson NRC/FSME/DWMEP/DURLD/RDB |
| To: | Brasel M Dairyland Power Cooperative |
| Hickman J, FSME/DWMEP,301-415-3017 | |
| References | |
| Download: ML102080325 (4) | |
Text
August 2, 2010 Mr. Michael A. Brasel, Plant Manager La Crosse Boiling Water Reactor Dairyland Power Cooperative S4601 State Highway 35 Genoa, WI 54632-8846
SUBJECT:
LA CROSSE BOILING WATER REACTOR - REVISED POWER REACTOR SECURITY RULE
Dear Mr. Brasel:
This letter is being sent as a follow on to the July 20, 2010 webinar on the applicability of the power reactor security regulations to Part 50 licensees. The purpose of this letter is to provide clarification on this issue and notify licensees of additional actions that may be required. The revised Power Reactor Security Rule (74 Federal Register (FR) 13926) became effective on May 26, 2009, with compliance required by March 31, 2010. The requirements in 10 CFR 73.55 are referenced in the protection requirements (10 CFR 72.212(b)(5)) for the general license issued under 10 CFR 72.210. The U.S. Nuclear Regulatory Commission (NRC) recognizes that some Part 50 licensees (e.g., a Part 50 licensee with a facility undergoing decommissioning or a Part 50 licensee that has only a general licensed Independent Spent Fuel Storage Installation (ISFSI) under 10 CFR 72.210 with no plant or a plant in decommissioned status) may not have recognized the applicability of the revised Power Reactor Security Rule to their facility. As a result, Part 50 licensees with facilities in decommissioning or decommissioned status may be out of compliance with the current 10 CFR 73.55 security requirements.
The NRC believes that there are currently no security or health and safety gaps at these facilities that may not be in compliance with the current 10 CFR 73.55 requirements. This is because the security programs at these facilities meet the baseline requirements of the previous version of 10 CFR 73.55 and also meet the requirements in subsequent security orders.
For facilities which may not be in compliance with the current 10 CFR 73.55, the NRC will consider, as appropriate on a case-by-case basis, the use of enforcement discretion in accordance with Section VII.B.6 of the Enforcement Policy, "Violations Involving Special Circumstances" for a period of time until the exemption process is completed. The NRC will consider a licensees demonstration of good-faith attempt to interpret and implement the new rule, the licensees prompt corrective actions, and the NRCs recognition of ambiguity regarding the scope of the rule when applying this discretion. Potential findings that are apparent violations of orders or applicable regulations and not attributable to good-faith interpretation and implementation problems, potential noncompliances that involve willfulness or deliberately uncorrected deficiencies, or potential noncompliances that either were not attributable to good-faith interpretation and implementation problems or involved willfulness will be dispositioned through the normal enforcement processes.
M.A. Brasel 2 Licensees need to evaluate the applicability of the current 10 CFR 73.55 to their specific facility and either make appropriate changes to the Physical Security Plan or ISFSI physical protection system or apply for exemptions, as necessary. As a matter of clarity, the new 10 CFR 73.55 rule does not obviate licensees from implementing the Additional Security Measures (ASMs) of 2007. Therefore, the requirements in the ASMs remain in effect. Exemptions granted to requirements in the previous version of 10 CFR 73.55 automatically transfer provided the language in 10 CFR 73.55 has not changed substantively. Consistent with past practice, NRC will consider allowing a licensee in a decommissioning status or a Part 50 licensee that has only a general licensed ISFSI under 10 CFR 72.210 with no plant or a plant in decommissioned status to decrease their security requirements through the exemption process.
The NRC expects that licensees will comply with the requirements in 10 CFR 73.55 or request exemptions from those requirements in 10 CFR 73.55 that the licensee believes are not applicable to their facility. Exemptions requests, and if applicable, license amendment requests should provide the basis for the request. Any necessary responses, exemption requests, or amendments must be submitted 120 days after receipt of this letter. Please contact John B. Hickman at 301-415-3017 or John.Hickman@nrc.gov with questions.
Sincerely,
/RA/
Bruce A. Watson, Chief Reactor Decommissioning Branch Decommissioning and Uranium Recovery Licensing Directorate Division of Waste Management and Environmental Protection Office of Federal and State Materials and Environmental Management Programs Docket No.: 50-409 License No.: DPR-45 cc: La Crosse Boiling Water Reactor Service List
M.A. Brasel 2 Licensees need to evaluate the applicability of the current 10 CFR 73.55 to their specific facility and either make appropriate changes to the Physical Security Plan or ISFSI physical protection system or apply for exemptions, as necessary. As a matter of clarity, the new 10 CFR 73.55 rule does not obviate licensees from implementing the Additional Security Measures (ASMs) of 2007. Therefore, the requirements in the ASMs remain in effect. Exemptions granted to requirements in the previous version of 10 CFR 73.55 automatically transfer provided the language in 10 CFR 73.55 has not changed substantively. Consistent with past practice, NRC will consider allowing a licensee in a decommissioning status or a Part 50 licensee that has only a general licensed ISFSI under 10 CFR 72.210 with no plant or a plant in decommissioned status to decrease their security requirements through the exemption process.
The NRC expects that licensees will comply with the requirements in 10 CFR 73.55 or request exemptions from those requirements in 10 CFR 73.55 that the licensee believes are not applicable to their facility. Exemptions requests, and if applicable, license amendment requests should provide the basis for the request. Any necessary responses, exemption requests, or amendments must be submitted 120 days after receipt of this letter. Please contact John B. Hickman at 301-415-3017 or John.Hickman@nrc.gov with questions.
Sincerely, Bruce A. Watson, Chief Reactor Decommissioning Branch Decommissioning and Uranium Recovery Licensing Directorate Division of Waste Management and Environmental Protection Office of Federal and State Materials and Environmental Management Programs Docket No.: 50-409 License No.: DPR-45 cc: La Crosse Boiling Water Reactor Service List Distribution:
DWMEP r/f C Lipa, RIII D Garner, NSIR ML102080325 OFC RDB/PM RDB/LA RDB/PM RDB/BC NAME JHickman CHolston CBanovac BWatson DATE 07/29/10 07 / 28 / 2010 07 / 29 / 2010 08/2/10 OFFICIAL RECORD COPY
La Crosse Boiling Water Reactor Service List cc:
Mr. William L. Berg Regional Administrator President and Chief Executive Officer Region III Dairyland Power Cooperative U.S. Nuclear Regulatory Commission 3200 East Avenue South 2443 Warrenville Road P.O. Box 817 Lisle, IL 60532-4352 La Crosse, WI 54602-0817 Mr. Thomas Zaremba Wheeler, Van Sickle and Anderson Suite 801 25 West Main Street Madison, WI 53703-3398 Mr. George Kruck Chairman, Town of Genoa S5277 Mound Ridge Road Genoa, WI 54632 Mr. Jeffery Kitsembel Electric Division Wisconsin Public Service Commission P.O. Box 7854 Madison, WI 53707-7854 Mr. Paul Schmidt, Manager Radiation Protection Section Bureau of Environmental and Occupational Health Division of Public Health Wisconsin Department of Health Services P.O. Box 2659 Madison, WI 53701-2659 Mr. Michael A. Brasel, Plant Manager La Crosse Boiling Water Reactor Dairyland Power Cooperative S4601 State Highway 35 Genoa, WI 54632-8846 Mr. Jeff McRill, Technical Support Engineer La Crosse Boiling Water Reactor Dairyland Power Cooperative S4601 State Highway 35 Genoa, WI 54632-8846